Introduction to Health Physics: Fourth Edition - Ruang Baca FMIPA UB

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where Ni = number of atoms of the ith element per cm 3 and Zi = atomic number of the ith element. For water, H2O, density = 1 g/cm 3 , formula weight = 18, we have and EXTERNAL RADIATION SAFETY 567 NH = 1cm 3 × 1 g 1 mol molecules × × 6.03 × 1023 × 2 cm3 18 g mol atom molecule NH = 6.7 × 10 22 atoms/cm 3 , NO = 0.5 × NH = 3.35 × 10 22 atoms/cm 3 . Substituting the numerical values into Eq. (10.34) gives Ze = 6.6, and substituting this value for Ze into Eq. (5.12a) gives us the fraction of the beta-ray energy that is converted into bremsstrahlung: f = 3.5 × 10 −4 × 6.6 × 2.27 = 5.24 × 10 −3 . If the bremsstrahlung is considered to radiate from a virtual point in the center of the solution, then the exposure dose rate at a distance d meters from this point is given by ˙D = f × E MeV s × 1.6 × 10−13 J MeV × μ m−1 3 s × 3.6 × 10 h 1.293 kg m 3 × 4π d2 × 1 J/ kg Gy × 10−3 Gy mSv , (10.35) where μ is the linear energy absorption coefficient for the quantum energy of the bremsstrahlung. In calculating bremsstrahlung dose rate for radiation safety purposes, we use the quantum energy corresponding to the average beta-ray energy, which in the case of 90 Y is 0.93 MeV. Using the value μ = 3.7 × 10 −3 m −1 (from Fig. 5-19), we use Eq. (10.35) to calculate the bremsstrahlung exposure dose rate at a distance of 0.5 m from the aqueous solution of 90 Sr— 90 Y to be 1.14 mSv (114 mrads) per hour. If we add a lead shield of thickness t cm, then the attenuation of the bremsstrahlung exposure dose rate can be calculated from Eq. (5.27), using a value of μ corresponding to the maximum energy beta particle. From Table 5-3, we find that μ = 0.51 cm −1 for 2.27 MeV. Thus, we have I = I0e −μt 0.1 = 1.14 × e −0.51×t t = 4.8cm. Use of a buildup factor in this case is not explicitly necessary, since it was assumed in the calculation of the shield thickness that all the bremsstrahlung had quantum
568 CHAPTER 10 energy equal to the maximum energy of the beta particles that gave rise to the Xrays. However, this quantum energy is, in fact, the upper limit of the bremsstrahlung energy, and all the bremsstrahlung is much lower in energy than this upper limit. The thickness calculated above, therefore, implicitly accounts for buildup through the use of an attenuation coefficient for the upper-energy limit of the X-rays rather than for their average energy. Neutrons Shielding against neutrons is based on slowing down fast neutrons and absorbing thermal neutrons. In Chapter 5, it was seen that attenuation and absorption of neutrons is a complex series of events. Despite the complexity, however, the required shielding around a neutron source can be estimated by the use of removal cross sections. (For neutron energies up to 30 MeV, the removal cross section is about three-quarters of the total cross section.) In designing shielding against neutrons, it must be borne in mind that absorption of neutrons can lead to induced radioactivity and to the production of gamma radiation (capture gammas) when the neutron is absorbed into a nucleus. W Example 10.13 Design a shield for an 18.5 × 10 4 MBq (5 Ci) Pu–Be neutron source that emits 5 × 10 6 neutrons/s, such that the dose rate at the outside surface of the shield will not exceed 0.02 mSv/h (20 μSv/h or 2 mrems/h). The mean energy of the neutrons produced in this source is 4 MeV. Solution Let us make the shield of water and compute the minimum radius for the case of a spherical shield. Since we know that the capture of a neutron by hydrogen produces a 2.26-MeV gamma ray, let us allow for the gamma-ray dose by designing the shield to give a maximum fast-neutron dose rate of 0.01 mSv/h (1 mrem/h), which corresponds to a fast flux of 3.7 neutrons/cm2 /s (Table 9-5). The total cross section for 4-MeV neutrons for hydrogen and oxygen are 1.9 and 1.7 b, respectively. Since water contains 6.7 × 1022 hydrogen atoms and 3.35 × 1022 oxygen atoms per cm3 , the linear absorption coefficient, , of water is = 1.9 × 10 −24 cm2 atom = 0.187 cm −1 , atoms cm2 atoms × 6.7 × 1022 + 1.7 × 10−24 × 3.5 × 1022 cm3 atom cm3
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INTRODUCTION TO Health Physics
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INTRODUCTION TO Health Physics Herm
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To my wife, Sylvia and to the memor
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CONTENTS Preface/ XI 1. Introductio
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Surface Contamination Limits/592 Wa
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PREFACE The practice of radiation s
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INTRODUCTION TO Health Physics
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INTRODUCTION 1 Health physics, radi
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REVIEW OF PHYSICAL PRINCIPLES MECHA
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REVIEW OF PHYSICAL PRINCIPLES 5 In
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and at v = 0.99 c, m = 9.11 × 10
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REVIEW OF PHYSICAL PRINCIPLES 9 Sub
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REVIEW OF PHYSICAL PRINCIPLES 11 Th
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REVIEW OF PHYSICAL PRINCIPLES 13 co
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REVIEW OF PHYSICAL PRINCIPLES 17 (t
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Electrical Current: The Ampere REVI
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Solution REVIEW OF PHYSICAL PRINCIP
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REVIEW OF PHYSICAL PRINCIPLES 23 Ac
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V a b REVIEW OF PHYSICAL PRINCIPLES
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Elastic Collision REVIEW OF PHYSICA
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Force Time REVIEW OF PHYSICAL PRINC
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REVIEW OF PHYSICAL PRINCIPLES 31 5
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REVIEW OF PHYSICAL PRINCIPLES 33 Fi
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REVIEW OF PHYSICAL PRINCIPLES 35 In
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or, in terms of the loss tangent,
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where Impedance t = time after clos
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REVIEW OF PHYSICAL PRINCIPLES 45 A
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therefore, Matter Waves REVIEW OF P
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SUMMARY REVIEW OF PHYSICAL PRINCIPL
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REVIEW OF PHYSICAL PRINCIPLES 53 Ac
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REVIEW OF PHYSICAL PRINCIPLES 55 2.
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REVIEW OF PHYSICAL PRINCIPLES 57 2.
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ATOMIC AND NUCLEAR STRUCTURE ATOMIC
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Bohr’s Atomic Model ATOMIC AND NU
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ATOMIC AND NUCLEAR STRUCTURE 63 2.
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The energy of this photon is E = hc
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ATOMIC AND NUCLEAR STRUCTURE 67 are
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ATOMIC AND NUCLEAR STRUCTURE 69 ene
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TABLE 3-1. Electronic Structure of
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ATOMIC AND NUCLEAR STRUCTURE 73 rad
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ATOMIC AND NUCLEAR STRUCTURE 75 spe
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ATOMIC AND NUCLEAR STRUCTURE 77 whe
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ATOMIC AND NUCLEAR STRUCTURE 79 neu
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SUMMARY ATOMIC AND NUCLEAR STRUCTUR
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ATOMIC AND NUCLEAR STRUCTURE 83 3.1
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R ADIATION SOURCES RADIOACTIVITY 4
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R ADIATION SOURCES 87 Figure 4-2. T
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R ADIATION SOURCES 89 Figure 4-3. R
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R ADIATION SOURCES 91 Figure 4-4. P
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Figure 4-7. Iodine-131 transformati
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R ADIATION SOURCES 95 Since positro
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R ADIATION SOURCES 97 level of high
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R ADIATION SOURCES 99 From the defi
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R ADIATION SOURCES 101 determined b
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R ADIATION SOURCES 103 sum of the l
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R ADIATION SOURCES 105 of activity
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Solution SA 14 10 226 × 1600 yea
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and the number of radioactive atoms
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W EXAMPLE 4.8 R ADIATION SOURCES 11
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TABLE 4-2. Neptunium Series (4n +1)
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TABLE 4-4. Actinium Series (4n +3)
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R ADIATION SOURCES 117 TABLE 4-6. A
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The integrand can be changed to the
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Figure 4-14. Secular equilibrium: B
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R ADIATION SOURCES 123 of the daugh
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R ADIATION SOURCES 125 By the use o
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Expanding and collecting terms, we
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R ADIATION SOURCES 129 Figure 4-17.
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Deflector Vacuum pump External deam
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Substituting the value of r from Eq
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R ADIATION SOURCES 135 before it is
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R ADIATION SOURCES 137 4.18. What w
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R ADIATION SOURCES 139 4.43. 100-mC
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R ADIATION SOURCES 141 Report No. 1
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INTERACTION OF RADIATION WITH MATTE
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INTERACTION OF RADIATION WITH M ATT
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TABLE 5-2. Bremsstrahlung Spectrum
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W EXAMPLE 5.12 INTERACTION OF RADIA
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Classification TABLE 5-6. α, n Neu
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W EXAMPLE 5.14 INTERACTION OF RADIA
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since ln E =−ξ, E 0 E E 0 = e
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where INTERACTION OF RADIATION WITH
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UNITS RADIATION DOSIMETRY 6 During
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Solution The radiation absorbed dos
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RADIATION DOSIMETRY 207 The relatio
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RADIATION DOSIMETRY 209 The use of
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RADIATION DOSIMETRY 211 Since one e
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RADIATION DOSIMETRY 213 Figure 6-5.
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The radiation absorbed dose rate fr
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RADIATION DOSIMETRY 217 Figure 6-6.
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219 TABLE 6-1. Mean Mass Stopping P
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RADIATION DOSIMETRY 221 The exposur
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W Example 6.9 RADIATION DOSIMETRY 2
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RADIATION DOSIMETRY 225 This calcul
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where ϕ = intensity at depth t, ϕ
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RADIATION DOSIMETRY 229 Assuming th
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When we combine the constants in Eq
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Solution RADIATION DOSIMETRY 233 Ph
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RADIATION DOSIMETRY 235 In most ins
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RADIATION DOSIMETRY 237 first-order
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RADIATION DOSIMETRY 239 Integrating
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Medical Internal Radiation Dose Met
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RADIATION DOSIMETRY 243 1 Bq/cm 3 o
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W Example 6.16 RADIATION DOSIMETRY
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for 131I listed in the output data
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then the total dose to the target o
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251 TABLE 6-8. Absorbed Fractions (
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RADIATION DOSIMETRY 253 which was f
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255 TABLE 6-9. S, Absorbed Dose per
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257 TABLE 6-10. S, Absorbed Dose Pe
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RADIATION DOSIMETRY 259 values of S
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RADIATION DOSIMETRY 261 S (kidney
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RADIATION DOSIMETRY 263 and MIRD Pa
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RADIATION DOSIMETRY 265 the 50-year
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TABLE 6-11. Synthetic Tissue Compos
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Solution Dn,p = The dose rate due t
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RADIATION DOSIMETRY 271 6.2. An air
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RADIATION DOSIMETRY 273 (a) Plot th
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RADIATION DOSIMETRY 275 the averag
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RADIATION DOSIMETRY 277 No. 7. Berg
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7 BIOLOGICAL BASIS FOR RADIATION SA
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BIOLOGICAL BASIS FOR R ADIATION SAF
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Na + K + BIOLOGICAL BASIS FOR R ADI
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TLC VC IC FRC IRV TV RV RV BIOLOGIC
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Capillary knot Vein BIOLOGICAL BASI
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Cell body One nerve cell Axon Nucle
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Aqueous humor Cornea Iris Lens Vitr
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Leucocytes and lymphocytes (x10 −
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TABLE 7-5. Tissue Dose Rate vs. Dis
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Birth Defects (Teratogenesis) BIOLO
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Cancer BIOLOGICAL BASIS FOR R ADIAT
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Incidence Incidence General form Do
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RADIATION SAFETY GUIDES 8 Radiation
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RADIATION SAFETY GUIDES 339 radiati
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RADIATION SAFETY GUIDES 341 members
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RADIATION SAFETY GUIDES 343 is a me
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RADIATION SAFETY GUIDES 345 Figure
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RADIATION SAFETY GUIDES 347 by radi
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RADIATION SAFETY GUIDES 349 radiati
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Dose Coefficient RADIATION SAFETY G
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RADIATION SAFETY GUIDES 353 appropr
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RADIATION SAFETY GUIDES 355 The cal
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Airborne Radioactivity RADIATION SA
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RADIATION SAFETY GUIDES 359 collisi
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RADIATION SAFETY GUIDES 361 is 1 g/
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RADIATION SAFETY GUIDES 365 can be
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RADIATION SAFETY GUIDES 367 total w
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RADIATION SAFETY GUIDES 369 TABLE 8
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compartment after a time t is given
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RADIATION SAFETY GUIDES 373 Now we
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RADIATION SAFETY GUIDES 375 classi
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RADIATION SAFETY GUIDES 377 normal
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RADIATION SAFETY GUIDES 381 whose c
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13 14 12 11 GI Tract 13 T RADIATION
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RADIATION SAFETY GUIDES 387 REGION
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RADIATION SAFETY GUIDES 389 The bb
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391 TABLE 8-18. Values of Absorbed
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TABLE 8-19. Summary of Dose Calcula
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TABLE 8-20. Dose Coefficients for S
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RADIATION SAFETY GUIDES 397 nation
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and the total activity in the body
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RADIATION SAFETY GUIDES 401 segment
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RADIATION SAFETY GUIDES 403 where E
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TABLE 8-22. Radioisotopes That Do N
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RADIATION SAFETY GUIDES 407 The sma
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RADIATION SAFETY GUIDES 409 TABLE 8
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RADIATION SAFETY GUIDES 411 Kentuck
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RADIATION SAFETY GUIDES 413 The fra
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RADIATION SAFETY GUIDES 415 ALI = 1
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W Example 8.10 RADIATION SAFETY GUI
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W Example 8.12 RADIATION SAFETY GUI
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RADIATION SAFETY GUIDES 421 Substit
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RADIATION SAFETY GUIDES 423 64. Inf
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RADIATION SAFETY GUIDES 425 16. Pro
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HEALTH PHYSICS INSTRUMENTATION RADI
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Gas-Filled Particle Counters HEALTH
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HEALTH PHYSICS INSTRUMENTATION 431
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TABLE 9-2. Scintillating Materials
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Figure 9-10. Block diagram of a sin
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DOSE-MEASURING INSTRUMENTS HEALTH P
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Response Normalized to Cs-137 10 Co
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Survey Meters: Ion Current Chambers
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W Example 9.6 HEALTH PHYSICS INSTRU
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NEUTRON MEASUREMENTS HEALTH PHYSICS
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467 TABLE 9-4. Threshold Foil React
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Count rate per unit flux 10 1 .1 .0
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Solution HEALTH PHYSICS INSTRUMENTA
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Neutrons TABLE 9-7. Calibration Sou
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Accuracy HEALTH PHYSICS INSTRUMENTA
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and is often expressed as a percent
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W Example 9.16 What is the MDA for
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Rearranging Eq. (9.60) and applying
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For the data in this example: HEALT
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Solution X = 1589 7 = 227 (Xi −
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10 EXTERNAL RADIATION SAFETY BASIC
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EXTERNAL RADIATION SAFETY 515 By th
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Page 540 and 541: Dose buildup factor, B Dose buildup
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Page 544 and 545: X-Rays EXTERNAL RADIATION SAFETY 52
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INTERNAL RADIATION SAFETY 617 In ce
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INTERNAL RADIATION SAFETY 619 In th
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INTERNAL RADIATION SAFETY 621 Since
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W Example 11.7 INTERNAL RADIATION S
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INTERNAL RADIATION SAFETY 625 In th
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INTERNAL RADIATION SAFETY 627 (b) A
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INTERNAL RADIATION SAFETY 629 a = c
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INTERNAL RADIATION SAFETY 631 treat
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INTERNAL RADIATION SAFETY 633 activ
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INTERNAL RADIATION SAFETY 635 Cohen
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INTERNAL RADIATION SAFETY 637 Repor
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CRITICALITY CRITICALITY HAZARD 12 O
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Potential energy E11 E12Em 2r Dista
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Fission Products CRITICALITY 643 Th
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CRITICALITY A2 = 2.35 × 10 15 1.2
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and will cause “fast fission.”
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W Example 12.3 CRITICALITY 649 Calc
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CRITICALITY 651 Making the very rea
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TABLE 12-3. Delayed Neutrons from t
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Power level dt t T τ then T = τ -
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CRITICALITY 657 TABLE 12-5. Activit
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TABLE 12-6. Minimum Critical Mass o
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SUMMARY CRITICALITY 661 a criticali
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CRITICALITY 663 12.10. The blood pl
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CRITICALITY 665 Knief, R. A. Nuclea
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EVALUATION OF RADIATION SAFETY MEAS
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Evaluation of Radiation Safety Meas
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W EXAMPLE 13.4 Evaluation of Radiat
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W EXAMPLE 13.9 Evaluation of Radiat
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SUMMARY Evaluation of Radiation Saf
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(b) Are the distributions normal or
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NONIONIZING RADIATION SAFETY 14 Non
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Solution NONIONIZING RADIATION SAFE
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NONIONIZING RADIATION SAFETY 725 hi
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2.4 mW cm 2 E mW cm 2 = (50 cm)2 (1
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NONIONIZING RADIATION SAFETY 729 Fi
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Figure 14-4. Beam cross sections fo
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% Total Transmission 100 90 80 70 6
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NONIONIZING RADIATION SAFETY 737 TA
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W Example 14.7 NONIONIZING RADIATIO
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NONIONIZING RADIATION SAFETY 745 Th
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TABLE 14-12. Reflecting Materials N
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Solution NONIONIZING RADIATION SAFE
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Solution The irradiance at the aper
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Wavelengths (nm) NONIONIZING RADIAT
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n = 300 pulses s × 10 seconds = 30
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% of Peak 100 80 60 40 20 NONIONIZI
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TABLE 14-16. Radar Bands FREQUENCY
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NONIONIZING RADIATION SAFETY 763 Al
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NONIONIZING RADIATION SAFETY 765 po
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NONIONIZING RADIATION SAFETY 767 Gr
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NONIONIZING RADIATION SAFETY 769 in
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Since there is 1 J/s in a watt, 1.1
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Biological Effects NONIONIZING RADI
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where Td = dry bulb temperature,
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NONIONIZING RADIATION SAFETY 779 to
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NONIONIZING RADIATION SAFETY 781 th
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Dosimetry NONIONIZING RADIATION SAF
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where S = power density, W/m 2 , ε
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NONIONIZING RADIATION SAFETY 791 ME
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where A = attenuation, dB, t = shie
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NONIONIZING RADIATION SAFETY 795 th
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NONIONIZING RADIATION SAFETY 797 14
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NONIONIZING RADIATION SAFETY 799 SO
Page 816 and 817:
NONIONIZING RADIATION SAFETY 801 Ha
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APPENDIX A Values of Some Useful Co
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APPENDIX B Table of the Elements NA
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Table of the Elements (Continued) A
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APPENDIX C The Reference Person Ove
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Chemical Composition APPENDIX C. 81
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Duration of Exposure 1. Occupationa
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APPENDIX D SPECIFIC ABSORBED FRACTI
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817 Energy in (MeV) Target 0.200 0.
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845 Target 0.200 0.500 1.000 1.500
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APPENDIX E TOTAL MASS ATTENUATION C
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APPENDIX F MASS ENERGY ABSORPTION C
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ANSWERS TO PROBLEMS 2.1 0.53 m/s to
Page 872 and 873:
TVL Al 5.3 cm 0.1 MeV Cu 0.6 cm
Page 874 and 875:
12.2 Nuclide Bq/L pCi/mL 24 Na 1200
Page 876 and 877:
INDEX Page numbers followed by “t
Page 878 and 879:
Catecholamines, 303 Cavity ionizati
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Energy Research and Development Adm
Page 882 and 883:
International Organization for Stan
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n-p junction, 445 Nuclear bombings
Page 886 and 887:
Radium injections, 324 Radon daught
Page 888:
Type 2, or non-insulin-dependent di
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Introduction to Health Physics: Fourth Edition - Ruang Baca FMIPA UB

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